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High Temperature Irradiation On A Zirconium Hydride 2 W O Uranium Alloy
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Book Synopsis High Temperature Irradiation of a Zirconium-hydride-2 W/o Uranium Alloy by : Gerald E. Lamale
Download or read book High Temperature Irradiation of a Zirconium-hydride-2 W/o Uranium Alloy written by Gerald E. Lamale and published by . This book was released on 1959 with total page 46 pages. Available in PDF, EPUB and Kindle. Book excerpt: Enriched ZrH/sub 1.65/ -2 wt.% uranium specimens were irradiated under 1 atm. of hydrogen at center-line temperatures between 900 to 1400 deg F to uranium burnups of between 13 and 25 at.%. Specially designed irradiation capsules were used to provide the conditions of temperature and hydrogen atmosphere which were required. Each capsule was instrumented with five thermocouples so that ample temperature data could be obtained during the irradiation. Almost negligible density changes were produced in the material by the irradiation. Changes in length and diameter were of a degree which could fall within experimental error in measurement. Metallographic examination showed no change in microstructure which could be attributed to the effect of irradiation. (auth).
Book Synopsis HIGH-TEMPERATURE IRRADIATION ON A ZIRCONIUM HYDRIDE-2 W/o URANIUM ALLOY. by :
Download or read book HIGH-TEMPERATURE IRRADIATION ON A ZIRCONIUM HYDRIDE-2 W/o URANIUM ALLOY. written by and published by . This book was released on 1959 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Enriched ZrH/sub 1.65/ -2 wt.% uranium specimens were irradiated under 1 atm. of hydrogen at center-line temperatures between 900 to 1400 deg F to uranium burnups of between 13 and 25 at.%. Specially designed irradiation capsules were used to provide the conditions of temperature and hydrogen atmosphere which were required. Each capsule was instrumented with five thermocouples so that ample temperature data could be obtained during the irradiation. Almost negligible density changes were produced in the material by the irradiation. Changes in length and diameter were of a degree which could fall within experimental error in measurement. Metallographic examination showed no change in microstructure which could be attributed to the effect of irradiation. (auth).
Book Synopsis HIGH-TEMPERATURE IRRADIATION ON A ZIRCONIUM HYDRIDE-2 W by :
Download or read book HIGH-TEMPERATURE IRRADIATION ON A ZIRCONIUM HYDRIDE-2 W written by and published by . This book was released on 1959 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Enriched ZrH/sub 1.65/ -2 wt.% uranium specimens were irradiated under 1 atm. of hydrogen at center-line temperatures between 900 to 1400 deg F to uranium burnups of between 13 and 25 at.%. Specially designed irradiation capsules were used to provide the conditions of temperature and hydrogen atmosphere which were required. Each capsule was instrumented with five thermocouples so that ample temperature data could be obtained during the irradiation. Almost negligible density changes were produced in the material by the irradiation. Changes in length and diameter were of a degree which could fall within experimental error in measurement. Metallographic examination showed no change in microstructure which could be attributed to the effect of irradiation. (auth).
Book Synopsis Effects of High Burnup at Elevated Temperatures on Uranium-0.52 and 1.62 W/o Zirconium Alloys by : J. H. Kittel
Download or read book Effects of High Burnup at Elevated Temperatures on Uranium-0.52 and 1.62 W/o Zirconium Alloys written by J. H. Kittel and published by . This book was released on 1959 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt: An investigation of the effects of irradiation on uranium containing 0.52 and 1.62 w/o zirconium was made. Specimens of wrought material, variously heat treated, were studied as well as castings of the alloys. It was found that, although the wrought and heat-treated alloys were reportedly stable under thermal cycling, they elongated rapidly under irradiation. The best material studied was the 1.62% alloy in the as-cast condition. It was found to increase in length initially at a rate of about 5% per a/o burnup, after which the rate steadily diminished. Up to burnups of at least 5.3 a/o it retained a smooth surface. Two specimens of the cast 1.62% alloy, one irradiated to 2.1 a/o burnup at a calculated central temperature of 690 deg C and the other irradiated to 5.3 at.% burnup at a calculated central temperature of 620 deg C, swelled and increased in volume with the formation of a large central void surrounded by highly porous metal. The critical swelling temperature of urauium--1.62 w/o zirconium alloy was found to lie between 300 and 620 deg C, with some indications that it may be near 500 deg C.
Book Synopsis The Reaction of Hydrogen with Zirconium-1 and -25 W/o Uranium Alloys by : Harold E. Bigony
Download or read book The Reaction of Hydrogen with Zirconium-1 and -25 W/o Uranium Alloys written by Harold E. Bigony and published by . This book was released on 1959 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis High-temperature Water and Steam-corrosion Behavior of Zirconium-uranium Alloys by : Stanley Kass
Download or read book High-temperature Water and Steam-corrosion Behavior of Zirconium-uranium Alloys written by Stanley Kass and published by . This book was released on 1959 with total page 28 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Pulse Heating of Zirconium-uranium Hydrides by : R. E. Taylor
Download or read book Pulse Heating of Zirconium-uranium Hydrides written by R. E. Taylor and published by . This book was released on 1962 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Rapid Pulse Heating of Modified Zirconium-uranium Hydrides to Destruction by : R. A. Finch
Download or read book Rapid Pulse Heating of Modified Zirconium-uranium Hydrides to Destruction written by R. A. Finch and published by . This book was released on 1965 with total page 60 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Unclassified U.S. Atomic Energy Commission Reports on the Metallurgy of Zirconium and Hafnium by :
Download or read book Unclassified U.S. Atomic Energy Commission Reports on the Metallurgy of Zirconium and Hafnium written by and published by . This book was released on 1957 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Pulse Heating of Modified Zirconium-uranium Hydrides by : R. E. Taylor
Download or read book Pulse Heating of Modified Zirconium-uranium Hydrides written by R. E. Taylor and published by . This book was released on 1963 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1974 with total page 1298 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Thermal Analysis of Uranium Zirconium Hydride Fuel Using a Lead-bismuth Gap at Light Water Reactors Operating Temperatures by : Brendan Melvin Ensor
Download or read book Thermal Analysis of Uranium Zirconium Hydride Fuel Using a Lead-bismuth Gap at Light Water Reactors Operating Temperatures written by Brendan Melvin Ensor and published by . This book was released on 2012 with total page 32 pages. Available in PDF, EPUB and Kindle. Book excerpt: Next generation nuclear technology calls for more advanced fuels to maximize the effectiveness of new designs. A fuel currently being studied for use in advanced light water reactors (LWRs) is uranium zirconium hydride (UZH), a fuel currently being used in the popular TRIGA research reactors. UZH is being considered because unlike the current fuel of choice, uranium dioxide, it is metal based and therefore better able to transfer the heat out of the fuel that is coming from fission. This can lead to lower operating temperatures which will reduce the amount of fission gas release to negligible quantities, eliminate cracking, and reduce the internal energy of the fuel. Furthermore, it is hoped the UZH will be better able to attain higher burnups, partly because of the presence of the strong moderator hydrogen, and thus will help better utilize resources and reduce the volume of nuclear waste produced. In order for UZH to be viable as a fuel it is recommended that the peak central temperature of the fuel be maintained below 650°C, at which point swelling due to void formation around the uranium atoms becomes a concern. In order to keep temperature below this level it has been proposed that lead-bismuth eutectic (LBE) be used as the gap material instead of helium. In order to ensure that the properties of UZH while using a LBE gap, specifically the thermal conductivity, do not degrade to the point of the fuel not being viable, an experiment was designed and put into the MIT research reactor. The initial results show a decreasing trend in thermal conductivity, albeit with much of this change considered to be because of the many thermal cycles the experiment underwent while in the reactor.
Book Synopsis The Transformation Kinetics of Uranium-zirconium Alloys Containing 50 and 60 WT PCT Uranium by : John J. Kearns
Download or read book The Transformation Kinetics of Uranium-zirconium Alloys Containing 50 and 60 WT PCT Uranium written by John J. Kearns and published by . This book was released on 1956 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Nuclear Science Abstracts written by and published by . This book was released on 1973 with total page 1162 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Influence of Heat Treatment on Irradiation-Induced Dimensional Changes in Some Uranium-Zirconium Alloys by : J. H. Kittel
Download or read book Influence of Heat Treatment on Irradiation-Induced Dimensional Changes in Some Uranium-Zirconium Alloys written by J. H. Kittel and published by . This book was released on 1957 with total page 13 pages. Available in PDF, EPUB and Kindle. Book excerpt: Specimens made of alloys containing 1, 2, and 3 weight percentage of zirconium in uranium were irradiated under conditions where the specimens were free from physical restraint. The specimens studied were from cast, wrought, and wrought and heat-treated materials. The heat treatments investigated included quenching from the gamma phase, quenching and tempering, isothermal transformations, and alpha phase annealing. All specimens were found to increase in length as a result of irradiation except a rolled and alpha-annealed group, which was observed to shorten. The rate of change of length with uranium atom burnup was found to depend strongly upon the prior metallurgical history of the specimens and upon their compositions.
Book Synopsis Effects of Irradiation on the Oxidation of Zirconium Alloys in High Temperature Aqueous Environments by : Atomic Energy of Canada Limited
Download or read book Effects of Irradiation on the Oxidation of Zirconium Alloys in High Temperature Aqueous Environments written by Atomic Energy of Canada Limited and published by . This book was released on 1965 with total page 35 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Book Synopsis Scientific and Technical Aerospace Reports by :
Download or read book Scientific and Technical Aerospace Reports written by and published by . This book was released on 1976 with total page 978 pages. Available in PDF, EPUB and Kindle. Book excerpt:
